|
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20205K4781999-04-0707 April 1999 Summary of 990204 Meeting with TVA Re Util Proposed risk-informed Inservice Insp Program for Browns Ferry Nuclear Plant,Unit 2 Piping & Solicit NRC Preliminary Comments on TVA Proposed Program ML20196K2781999-01-0404 January 1999 Summary of 981217 Meeting with Util to Discuss Plans & Activities Re Spent Fuel Storage at Plant.List of Attendees & Handouts Encl ML20236Q6591998-07-10010 July 1998 Summary of 980709 Meeting W/Tva Re Browns Ferry Nuclear Plant License Amend Request for Power Uprate.List of Attendees & Request for Addl Info,Encl ML20236F7861998-06-30030 June 1998 Summary of 980623 Meeting W/Vynp Re Plans & Activities Related to long-term Spent Fuel Storage Plans.List of Attendees & Copies of Handouts Distributed at Meeting Encl ML20248F1581998-05-27027 May 1998 Summary of 980520 Meeting W/Tva Re Browns Ferry Nuclear Plant License Amend Request for Power Uprate & Primarily Focused on Instrumentation Issues ML20247M9251998-05-18018 May 1998 Summary of 980508 Meeting W/Tva Re Operation of Plant, Status of Several Licensing Actions & Activities Including TVA Plan to Implement Improved STS by 980701 ML20217D4741998-04-20020 April 1998 Summary of 980414 Meeting W/Participants to Discuss Licensee Amend Request for Conversion of Custom TS to Improved Std TS ML20216H5751998-04-16016 April 1998 Summary of 980407 Meeting W/Vynp Re Plans & Activities Re Assurance of Adequate Net Positive Head for Certain safety- Related Pumps.List of Meeting Attendees & Copies of Meeting Handouts Encl ML20216E8591998-04-14014 April 1998 Summary of 980326 & 27 Meeting W/Util to Discuss Technical & Working Level Nature Re Conversion of Custom TS to Improved Std Ts.List of Attendees Encl ML20217J9111998-03-31031 March 1998 Summary of 980324 Meeting W/Representative of Vynpc Re Torus Strainer Installation,Post Installation Torus Testing & Containment Analysis Methodology.List of Attendees & Handouts Distributed at Meeting IR 05000259/19970041998-02-0606 February 1998 Summary of 980126 Meeting W/Tennessee Valley Authority Re Resolution of Unresolved Issue 50-290/97-04-01 Identified in Insp Rept 50-259/97-04.List of Attendees Encl ML20198Q5211997-11-0505 November 1997 Summary of 971103 Meeting W/Vynpc in Rockville,Md on Plans & Activities Re Submittal & Implementation of Improved TS at Plant.List of Attendees,Handout of Plant Presentation & W Beckners Comments Encl ML20211P4991997-10-0909 October 1997 Summary of 970917 Meeting W/Vynp in Rockville,Maryland Re ASME Code Case N560.List of Meeting Attendees,Meeting Agenda & Meeting Handouts Encl ML20141H9321997-07-29029 July 1997 Summary of 970722 Meeting W/Tva in Rockville,Md Re Plans for Submittal of License Amends Supporting Power Uprate & 24 Month Fuel Cycles for Mentioned Plant.List of Attendees & TVA Handout Encl ML20141G4061997-06-30030 June 1997 Summary of 970521 Meeting W/Tva in Rockville,Md Re Review of Section 3.3 of Improved TS for Mentioned Plant.List of Attendance & Comments Encl ML20137P3501997-04-0707 April 1997 Summary of 970327 Meeting W/Tva in Rockville,Md Re ECCS Suction Strainers Mod for Plant,Units 1,2 & 3.List of Attendees & Handouts Encl ML20137X1131997-04-0303 April 1997 Summary of 970326 Meeting W/Vynp in Rockville,Md to Discuss Licensee Engineering,Improved Ts,Correction Actions & Plant Goals for 1997.List of Attendees & Presentation Matls Encl ML20133M4341997-01-16016 January 1997 Summary of 961223 Meeting W/Vynp Re Licensee Request to Be Briefed on Vynp Plan for Analysis in Preparation for Vermont Yankee Fuel Cycle 20 Reload.List of Attendees & Handouts Encl ML20129E5901996-10-24024 October 1996 Summary of 961016 Meeting W/Tva in Rockville,Md Re Recent TVA Efforts to Validate Info in Browns Ferry Updated Final Safety Analysis Rept Prior to Submittal of Periodic Update Planned for 961022.List of Attendees & Handouts Encl ML20129H1091996-10-0202 October 1996 Summary of 960926 Meeting W/Tva in Rockville,Md Re Recent Denial of Emergency TS Amend Request for Bfn.List of Attendees Encl ML20129G7761996-08-0909 August 1996 Summary of 432nd ACRS Meeting on 960612-14 Re Severe Accident Research & Draft Reg Guide DG-1047, Std Format & Content for Application to Renew Nuclear Power Plant Operating Licensees ML20129G6021996-06-26026 June 1996 Summary of 431st ACRS Meeting on 960523-25 Re Potential Ipe/ IPEEE Results to Compare Risk of Current Population of Plants W/Safety Goals,Resolution of Multiple Sys Responses Program Issues & Proposed Rule on Shutdown Operations ML20217D2601996-06-10010 June 1996 Summary of 960521 Meeting W/Listed Attendees Re Completion of Post Restart Issues & Lessons Learned from Restart Process ML18038B3511995-06-0606 June 1995 Trip Rept of 950514-16 Visit to Browns Ferry Nuclear Power Stations Re Blast Evaluation & Subsequent Vehicle Barrier Location ML20058G9441993-12-0707 December 1993 Summary of 931110 Meeting W/Tva in Rockville,Md Re TVA Plans to Improve Quality of Licensing Submittals for Bfn.List of Attendees & Handouts Encl ML20059L8351993-11-0909 November 1993 Summary of 931025 Meeting W/Util in Bolton,Ma Re Status of Open Licensing Issues Involving Plant.Attendees Listed in Encl 1 ML20057D0761993-09-27027 September 1993 Summary of 930903 Meeting W/Util in Rockville,Md Re Ways Util Might Improve Quality & Completeness of Plant Licensing Submittals.List of Meeting Attendees & List of Specific Licensing Submittals Discussed During Meeting Encl ML20058M1861993-09-22022 September 1993 Summary of Operating Reactors Events Meeting 93-35 on 930915 ML20056F9221993-08-26026 August 1993 Summary of 930803 Meeting W/Util in Rockville,Md Re Proposed Cost Beneficial Security Program Revs at Browns Ferry Nuclear Plant.List of Attendees & Meeting Handouts Encl ML20056D9801993-07-30030 July 1993 Summary of 930720 Meeting W/Util in Rockville,Md to Discuss Plans & Schedule to Implement Improved STS at Plant.Meeting Attendees Listed in Encl 1 ML20056D8341993-05-26026 May 1993 Summary of Operator Reactors Event Meeting 93-18 on 930519 ML20056D9841993-05-18018 May 1993 Summary of Operating Reactors Events Meeting 93-17 on 930512 ML20128E7681993-02-0404 February 1993 Summary of 921216 Meeting W/Vynp in Rockville,Md Re Licensing Issues Related to Plant.List of Attendees Encl ML20126K4291992-12-30030 December 1992 Summary of 921201 Meeting W/Util in Rockville,Md Re Discussions on Proposed Upgrade of Refueling Floor & RB Radiation Monitoring Equipment,Including Proposed Revs to Plants TS Submitted in Ltr ML20126K4431992-12-30030 December 1992 Summary of 921216 Meeting W/Util in Rockville,Md Re Discussions on Design & Operation of Plant Hardened Wetwell Vent.List of Attendees & Meeting Agenda Encl ML20125D0341992-12-0202 December 1992 Summary of 921015 Meeting W/Util in Rockville,Md Re Util Plans for Conducting Expanded IPE for Plant.List of Attendees & Meeting Handouts Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20058M4491990-08-0808 August 1990 Summary of 900727 Meeting W/Util on Site Re Plant Tour. Restart Status & Condition of Unit 2 Primary Focus of Site Tour.List of Attendees Encl ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20248B5171989-08-0303 August 1989 Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20248E0351989-08-0202 August 1989 Summary of 890710,11 & 12 Meetings W/Util at Plant Site Re Electrical Issues,Including Cable Ampacity & Ac/Dc Electrical Distribution Necessary to Support Full Power Operation.Agenda,List of Attendees & Handouts Encl ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl IR 05000259/19890101989-06-29029 June 1989 Summary of 890606 Meeting W/Util in Rockville,Md Re Handling of Clay Pipe Issue & Condition Adverse to Quality Program, Per Findings in Insp Repts 50-259/89-10,50-260/89-10 & 50-296/89-10.List of Attendees & Presentation Slides Encl ML20245K3021989-06-22022 June 1989 Summary of 890615 Meeting W/Util in Rockville,Md Re Proposed Tech Spec Change 251 Dealing W/Table 3.7.A, Primary Containment Isolation Valves ML20246F8691989-06-22022 June 1989 Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2 1999-04-07
[Table view] Category:TRIP REPORTS
MONTHYEARML18038B3511995-06-0606 June 1995 Trip Rept of 950514-16 Visit to Browns Ferry Nuclear Power Stations Re Blast Evaluation & Subsequent Vehicle Barrier Location ML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20154L1661988-05-10010 May 1988 Trip Rept of 880412-15 Mgt Team Visit to Plant Sites,Two Matls Licensees & Region I Ofcs.List of Team Members & Summary of Observations & Perceptions from Visit Encl.Info Deleted ML20153B0021988-03-14014 March 1988 Trip Rept of 880222-26 Site Visit Re Audit of Control Room Design & Procedures Generation Package ML20147F4191988-03-0202 March 1988 Trip Rept of 880224-25 Site Visit,Listing Activities & Key Points,Including Attendance at Sequoyah Operational Readiness Public Meeting,Tracking of Appropriate Lessons Learned from Plant & Identification of Criteria Issues ML20196F9951988-02-24024 February 1988 Partially Withheld Trip Rept of 880209-11 Mgt Team Visit to Region V & San Onofre & Trojan Sites Re Integrated Assessment of Mgt Effectiveness Associated W/Regionalized NRR & NMSS Programs ML20149J8311988-02-11011 February 1988 Trip Rept of 880204-05 Site Visit Re Training Course on Health Physics,Proposed Agenda for Audit of Control Room Procedures Generation Package & Nuclear Performance Plan ML20238C8361987-12-28028 December 1987 Trip Rept of 871208-10 Site Visit Re Fire Protection Program,Restart Tech Specs,Calculations program,II.K.3.18 Mods & Working Level Meetings on Fire Protection & Seismic Design ML20236Q4581987-11-10010 November 1987 Trip Rept of 871028-30 Visit to Plant Site ML20236N1351987-11-0909 November 1987 Trip Rept of 871028-29 Site Visit to Attend Presentation on Restart Testing W/J Watt to Discuss Differences Between Sequoyah & Browns Ferry Program.Program Description Presented by Util Encl ML20151W0041987-03-12012 March 1987 Submits After Trip Rept IA-86-778, Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl1986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl ML20213F8661986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl ML20206J6561986-06-23023 June 1986 Trip Rept of 860612 Training Session in Lacey,Wa Re Federal Radiological Emergency Response Plans & Meeting W/Utils & State of Wa Concerning Potential Emergency Preparedness Issues.Attendees Listed & Training Agenda Encl ML20244D8391986-05-0707 May 1986 Trip Rept of 860415 Site Visit Re Demonstration for Ultrasonic Exam Procedure of Statically Cast Stainless Steel Primary Loop Welds.Issue of Preservice Ultrasonic Exam of Welds Resolved.Trip Repts by Inel & Bnwl Encl ML20244D8401986-04-22022 April 1986 Trip Rept of 860415 Site Visit Re Demonstration of Ultrasonic Exams Performed on Cast Stainless Steel Primary Piping Welds.Exam Procedure Appears to Meet or Exceed ASME Code Requirements.Written Procedure Not Available ML20154L9181986-03-0606 March 1986 Trip Rept of 851021-24 Site Visits Re Wrong Unit/Wrong Train Events to Determine Whether Simple,Low Cost Improvements Can Be Identified & Implemented ML20237C9681986-02-19019 February 1986 Trip Rept of Attendance at State of Il 860213 Meeting Re Training Session on NRC Incident Response Program & NRC Participation in 860408 Plant Emergency Exercise.List of Attendees & Partial Agenda Encl ML20141H8551986-01-10010 January 1986 Trip Rept of 851112-15 Site Visits Re Wrong Unit/Wrong Train Events.Visit Conducted as Part of short-term Effort to Determine If Low Cost Improvements Can Be Identified & Implemented to Reduce Frequency of Events ML20137D4761986-01-10010 January 1986 Trip Rept of Observation of INPO Accreditation Team Visit During Wk of 850930-1004 of Util Power Plant Training Programs.List of INPO Evaluation Team Members Encl ML20138A1201985-09-23023 September 1985 Trip Rept of 850617-20 Site Visits Re Reduction of Wrong Unit/Wrong Train Events at Facilities ML20199G3181985-01-15015 January 1985 Trip Rept of 841114-16 Site Visit Re Meetings W/Qa/Qc Inspectors to Emphasize That All Safety Issues Must Be Resolved Before Units Can Be Licensed ML20127B5101984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed IA-85-160, Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed1984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed ML20138M9741983-12-20020 December 1983 Trip Rept of 831129-30 Site Visit Statistical Analysis of Backfit Insp Program ML20205T5371983-02-15015 February 1983 Trip Rept of 830126 Meeting in Bethesda to Discuss Question of Corrective Actions to Be Required of Util Re Finding of Uncertified QC Inspectors at Site ML20134B4611982-09-16016 September 1982 Trip Rept of 820830-31 Visit to Bechtel,Norwalk,Ca to Observe Region IV Insp Concerning Effectiveness of Util/ Bechtel Processing of Field Change Notices for Facility Const.Supporting Documentation Encl ML18139B9671982-07-13013 July 1982 Trip Rept of 820512-14 Visit to Facilities Re Radiological Effluent Tech Specs ML20213D9361981-12-0707 December 1981 Trip Rept of 811005 Visit to Denver,Co & Richland,Wa to Discuss Site Drainage Plans,Meeting W/Westec Consultants on Possible Orographic Effects & Duration of Rainfall & Meeting W/Pnl to Discuss Safety & Environ Review Procedures ML20140G2531976-06-28028 June 1976 Trip Rept of 760614-17 Site Visits Re Relief Valve Test Sequence.Test Results Encl ML20140G2591976-06-15015 June 1976 Trip Rept of 760529 Site Visit Re Witness of Safety/Relief Valve Tests.List of Attendees Encl ML20235C1831975-11-24024 November 1975 Trip Rept of 751111 Visit to Plant Site as Part of Q-1 Review Procedures Re Status of Plant Const.List of Participants Encl ML20235C1511975-10-21021 October 1975 Trip Rept of Site Visit During Wk of 751006 Re NRC Concerns & General Overview by Util of Const Activities.Summary of Site Visit Schedule & Participating Personnel Encl ML20126D8131973-05-0101 May 1973 Trip Rept of 730424-25 Site Visit to Obtain First Hand Knowledge of Site & Environs & to Discuss Possible Problem Areas.Attendance List Encl ML20210B3761972-12-29029 December 1972 Trip Rept of 721218 Site Visit Re Jet Pump Assembly & Torus Ring Header Sys.Dynamic Analysis & Measured Data Not Available.Results & Findings Will Be Described in Rept Scheduled for 730302 ML20210B2621972-10-25025 October 1972 Trip Rept of 721019 Visit to Plant to Investigate Ring Header Problem & Observe GE Blowdown Tests ML20084K2751971-01-27027 January 1971 Trip Rept of 710120 Visit to Plant Re Plans for Replacement of Dome Concrete & Review of Specs for Work.Concrete Removal Operation Satisfactory ML20234E3591964-04-29029 April 1964 Trip Rept of 640318 Visit to Bodega Reactor Site Re Geology of Area. Statement on Bodega Head Power Site Shaft Fault, Encl 1995-06-06
[Table view] |
Text
__
. ( /
. JUL 311986 Enclosure 1 TRIP REPORT PURPOSE: To Discuss Browns Ferry Seismic Design Issues PLACE: Browns Ferry Plant Site. Decatur, AL.
4 DATE: May 14 and 15, 1986 TEAM: R. Hermann, J. Tsao, S. Kim Engineering Branch, DBL, NRR j During May 14 and 15 1986, the NRC staff, TVA personnel, and TVA consultants met i
at Browns Ferry site to discuss seismic design issues. A list of the meeting attendance is attached (Attachment 1). Attachment 2 is the handouts from TVA.
- There are currently five issues relating to Browns Ferry seismic design; cable trays, conduit, HVAC, control rod drive return lines and IEB issues (79-14 and 79-02).
s Prior to discussing details of the issue, the staff requested that TVA present a comprehensive background history of the issues leading up to the current reanalysis and fixes. It was apparent that they were not prepared to discuss past history in detail at the meeting. Consequently, the staff requested TVA to provide such background information in all their future submittals at the time of resolution of each issue. They agreed to do so. Also, the staff informed TVA that all the design criteria change and establishment of interim criteria or operability should be discussed with the staff for approval prior to implementation.
TVA and the staff discussed having a meeting at Bethesda to review the overall seismic re evaluation of the plants. We expect the licensee will identify any changes to the building models as well as any other changes to the original l FSAR seismic criteria that are under consideration. TVA pointed out that while cable trays were evaluated based on the original stick model response, the response spectra for the piping analysis (79-14) were derived from a new building structural model. The staff was not aware that TVA has been working on a new building model.
After concluding the meeting on May 15, the staff toured the plant; specific-ally, the cable spreading room and CRD piping arrangement in the reactor bull. ding and. cable trays in the intake structure. It was observed that fire .
retardant spray on cable is a stiff and brittle material. The coating material may have a tendency to increase stiffness of the cable tray system and tends to .
l limit damping by the cable. Considering the increased stiffness, it appears -
that the 7% damping used appears more reasonable than the 15% or 20% damping value for the cable trays analysis at other facilities. -
- Attachments 1 and 2 not included 8611170221 861112 PDR FOIA CRABEH86-778 PDR
.- . _ T_X . _._L ._ L __ - ___ _ _ _ - __ _ . _.
l i ,
2 Following is a briof description of each issue. Their resolution efforts are still in progress.
- 1. Cable Trays United Engineers, a contractor for TVA, presented interim criteria and associa-ted 14 fixes. They plan to complete the fixes prior to projected September 1986
' startup. The staff received a 5 volume submittal transmitted to us by TVA's May 2, 1986, letter to D.R. Muller of NRC. The slides used for the presenta-tion are similar to the ones used in the October 1985, Bethesda meeting. We were told by TVA that there were no seismic design requirements originally for the ceble trays. However, they initiated a backfit program in about 1970 and subsequent inspection revealed that the field implementation of backfit was unsatis factory. TVA hired United Engineers to establish the interim criteria and to fix the cable trays to support startup of Unit 2. We requested that the background information as well as the licensee's intended long term corrective mally.
actions and the schedule for their implementation be provided for-
- 2. Conduit Qualification Program Erowns Ferry conduits were not designed for earthquakes originally. Several segments of the full size corduits were tested on shaker table at W'yle Labora-tory for DBE, 80% and 100% of table capacity. The table capacity of the shaker is rated at approximately 8 times of vertical DBE and 2.5 times of the horizon-tal DBE. Arrangements of tte conduit tested are provide in the Attachment 2.
None of the conduits failed except two supports of a conduit at 100% table capacity. TVA will provide a submittal to the NRC with a similiar content to that described for the cable trays.
- 3. HVAC Concerns TVA has initiated a program to review seismic design of the HVAC. As was the case for the etnduits the HVAC ducts were not originally seismically designed but were later backfit. The licensee has instituted a program to identify discrepancies beteeen the installed system and the backfit design. TVA is currently developing a program to resolve this issue and will provide it to the staff for review and approval.
- 4. Control Rod Drive (CRD) Return Lines As a result of an NRC information notice, TVA hired a contractor, IMPELL, to re-evaluate the seismic design of the CRD piping. TVA is using 5% damping factor in the seismic re-analysis of the CRD piping. The staff requested TVA to provide their bases for this damping value, a summary of the results of the analysis, a list of intended modifications, and a schedule for their completion.
l l
s e
t
( ..
. 3
- 5. I & E Bulletin 79-14 And 79-02 TVA presented the plan of attack to resolve the I & E Bulletin 79-14 and 79-02.
Three phases have been planned: Phase I is the initial "walkdown" of the existing piping system to obtain the inspection data of the existing piping and ascertain " operability" of the system.
Phase II is the reanalysis of the piping system. TVA stated that it intends to use Section III,1971 and 1973 addendum of the ASME Code to analyze thermal, dead weight, and seismic effects for the piping system. However, TVA did not specify whether they will analyze for the seismic anchor movement or LOCA loads. It was unclear from the meeting if TVA intends to change the floor response spectra and damping factors for the reanalysis. TVA did provide a draft copy of their current reevaluation interim report. -
Phase III is the modification phase using the results from the piping stress analysis.
The staff expects TVA to provide a concise description of their re-evaluation criteria and identify any changes from that described in the FSAR, a statement confirming that all operability evaluation are complete, and a schedule for completion of Phases I, II & III of the program.
- 6. Non-essential Piping Test TVA initiated a vibration test program for the non-essential piping to deter-mine if the piping would survive a DBE. This work was intended to resolve the issue of class II piping damaging class I piping and components as a result of a severe earthquake.
Pipes with 2, 4 and 6 inch diameter were supported on a simulated concrete wall and were placed on the shaker table. From the results of the tests, the j non-essential piping system configurations appear to have a significant inherent capability to withstand seismic excitation. I l
l O
e e
l l
m , _ . - - - - -, , _ - - - - - - , . - - - , , - - _ - - - , _ - - - - , , . , - - - ,-,-,_,_,,p _
f
- t. .
. JUL 81586
. Enclosure 2 Browns Ferry Nuclear Plant Seismic Design Issues Reques_t for Additional Information The numbered items in the following request are consistent with the meeting summary (enclosure 1) transmitted by the same letter:
- 1. Cable Trays - please provide background information, the TVA long term corrective actions and the implementation schedule regarding the seismic design of the cable trays.
- 2. Conduct Qualification Program - please provide information similar to item 1 above for the conduct qualification program.
- 3. HVAC Concerns - please provide the program to identify discrepancies between the installed system and the backfit design for staff review and approval.
- 4. Control Rod Drive (CRD) Return Lines - please provide the basis for the 5% damping factor used in the seismic reanalysis of the CRD piping, a summary of the results of the analysis, a list of intended modification and a schedule for completion of the modifications.
- 5. IE Bulletins 79-14 and 79 please provide a concise description of the reevaluation criteria for the piping system with identification of changes from the FSAR, a statement confirming that all operability evaluations are complete, and a schedule for completion of Phases I, II and III of the program.
1 l
1
=
l l
1
\
{ s i
ENCLOSURE i
REQUEST FOR ADDITIONAL INFORMATION FOR VERMONT YANKEE RELATING TO HIGH DENSITY RACK - 5 PENT ' FUEL POOL EXPANSION ,
DOCKET NO. 50-271 l
Reference:
" Vermont Yankee Spent Fuel Storage Rack Replacement Report" April, 1986.
- 1) There are three load combinations provided in the report; pages 20, 71 and 88. Please discuss why there exist variations among three combinations and state which one was used for the rack design . Currently, the staff review is based on 1979 NRC position paper together with ASME Section III, subsection NF,1980 for stress limits. .
-2) It appears that there are errors in stress limits associated with the load combination in page 72. Sy is not allowed for levels A and B stress limits. Please clarify. .
- 3) Definition of S (section strength) is not clear. Provide an example and a justification for using S as a stress limit. (page 72) l l
- 4) It is stated that "the nonlinear three-dimensional model adequately represent the effects of impacting, friction and hydrodynamic coupling" (p. 74). Provide mathematical expressions for each component and discuss how such expressions are coded into the enmputer program. Provide experimental evidence that such mathematical expression together with numerical solution employed in the program indeed represent physical behaviors.
l 5) Provide a stability analysis for the nonlinear equation that governs rack dynamic response (p. 75-76). One should demonstrate that small changes in input parameters do not result into large changes in resultant values such as sliding and uplift of the rack. Parameters one should consider are damping, friction or any other major input such as forces and forcing frequencies. Some examples of stability analysis are demonstrated in
, " Nonlinear Vibration" by J.J. Stoker, Interscience Publishers and "
Analysis of Numerical Methods" by Isaacson and Keller, John Wiley.
W l
p\
r
(
9 2-i
~
- 6) It is ' stated in the report (p. 90) that " Euler bucklin'g load for one storage cell is 105.7k". Provide a calculation for the buckling. load together with a schematic orasing of the mathematical model. Demonstrate that a dynamic effect of dropped fuel assembly is considered in'the buckling calculation.
- 7) In the report (p. 75), it is stated that "three conditions of fuel storage were analyzed; full, half full and empty. Consider a case where only two or three extreme outer cells are loaded while rest of the cells are empty. Demonstrate that the rack- does not tip over considering the fact that the rack support pads are recessed from the outer edge of the rack.
9
v Mr. R. H. Capstick Vemont Yankee Nuclear Power Corporation Vermont Yankee Nuclear Power Station -
cc:
Mr. J. G. Weigand W. P. Murphy, Vice President &
President & Chief Executive Officer Manager of Operations Vermont Yankee Nuclear Power Corp. Vermont Yankee Nuclear Pcwer Corp.
R. D. 5, Box 169 R. D. 5, Box 169 Ferry Road Ferry Road Brattleboro, Vemont 05301 Brattleboro, Vernont 05301 Mr. Donald Hunter, Vice President Mr. Gerald Tarrant . Comissioner Vermont Yankee Nuclear Power Corp. Vermont Pepartment of Public . Service 1671 Worcester Road 120 State Street Framingham, Massachusetts 01701 Montpelier, Vemont 05602 New England Coalition en Nuclear Pollution Hill and Dale Farm Public Service Board R. D. 2 Box 223 State of Yemont Putney, Vemont 05346 120 State Street Montpelier, Vermont 05602 Mr. Walter Zaluzny Chairman, Board of Selectrian Yemont Yankee Decornissionirg Post Office Box 116 Alliance Vernon, Vemont 05345 Box 53 Montpelier, Verront 05602-0053 J. P. Pelletier, Plant Manager Vemont Yankee Nuclear Power Corp.
Post Office Box 157 Resident Inspector Vernon, Vement 05354 U. S. Nuclear Regulatory Corcission Post Office Box 176
{ Raymond N. McCandless Vernon, Verront 05354 Vermont Division of Occupational A Radiological Health Yemont Public Interest Administration Building Research Group, Inc.
10 Baldwin Street 43 State Street Montpelier, Vemont 05602 Montpelier, Yermont 05E0?
Honorable John J. Easton Thomas A. Murley Attorney General Regional Adninistrator State of Vermont Recion I Office
~
109 State Street U. S. l'uclear Regulatory Corrission l Montpelier, Vermont 05602 631 Park Avenue l
King of Prussia, Pennsylvania 19406 John A. P.itscher, Esquire Ropes & Gray l 225 Franklin Street .
l Boston, Massachusetts 02110
g' (
[.'
- Mr. S. A. White Browns Ferry Nuclear Plant Tennessee Valley Authority Units 1, 2, and 3 cc: ,
- r
- 11. S. Sanger., Jr. , Escuire W. C. Bibb General Counsel Site Director, BFNP Tennessee Valley Authority Tennessee Valley Authority 400 Comerce Avenue Post Office Box 2000 E 11B 330 Decatur, Alabana 35602 Knoxville, Tennessee ~37902 Resident Inspector Mr. Ron Rooers U. S. Nuclear Reaulatory Commission Tennessee Valley Authority Route 2. Box 311 SN 130B Lookout Place ~
Athens, Alabama 35611 Chattanooga, Tennessee 37402-2801 Mr. Donald L. Hi111ans, Jr.
Tennessee Valley Authority -
Chairman, Limestone County Comission 400 West Sumit Hill Drive, U10BB5 Post Office Box 188 Knoxville, Tennessee 37902 Athens, Alabana 35611 Robert L. Lewis,tianaper, BFNP Ira L. Meyers, M.D. Tennessee Valley Authority State Health Officer Post Office Box 2000 State Department of Public flealth Decatur, Alabama 35602 State Office Buildino Montnomery, Alabama 36130 Mr. K. H. Whitt E3A8 400 West Sunnit liill Drive Tennessee Valley Authority Knoxville, Tennessee 37902 Regional Administrator, Region II U. S. fluclear Regulatory Comission l
101 Marietta Street, Suite 3100 Atlanta, Georoia 30303 l
l Mr. Steven Roessler U. S. Nuclear Regulatory Comission Reactor Training Center Osborne Office Center, Suite 200 Chattanoona, Tennessee 37411 1 .
l l
l l . . _ _ _ - . _ _ _ .-_. . - _ _ . _ _ - _ _ - - - _ _ _ _ . _- _ - - _ - .